ML20052C464

Supplemental Responses to Wi Environ Decade First Interrogatories & Request for Production of Documents Re full-scale Sleeving Program

ML20052C464
Person / Time
Site:	Point Beach
Issue date:	04/30/1982
From:	Churchill B SHAW, PITTMAN, POTTS & TROWBRIDGE, WISCONSIN ELECTRIC POWER CO.
To:	WISCONSIN'S ENVIRONMENTAL DECADE
Shared Package
ML20052C465	List: ML20052C464 ML20052C467
References
NUDOCS 8205050012
Download: ML20052C464 (10)

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

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WISCONSIN ELECTRIC POWER COMPANY ) Docket Nos. 50-266 o

) 50-301 9 'MM/'/ q (Point Beach Nuclear Plant, ) (OL Amendnent) ^ '

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l 5 LICENSEE'S SUPPLEMENTAL RESPONSES TO DECADE /S  ! 'S 1 FIRST INTERROGATORIES AND REQUEST FOR T,\ , ,

PRODUCTION OF DOCUMENTS ON THE FULL-SCAL ',3)

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,f3 SLEEVING PROGRAM \

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Licensee herein is providing supplemental information in response to Decade's above-capti~oned Interrogatories No. 7, 8, 10, 13, 14, 17 and 18 which Licensee has obtained subse-quently to its March 1, 1982 response.

Copies of identified documents are available for in-spection at the offices of David K. Porter, Wisconsin Electric

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Power Company, 231 West Michigan Street, Milwaukee, Wisconsin.

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B205050012 820430 1 PDR ADOCK 05000266 0 PDR

7. State the preliminary and final results of tests performed (i) to demonstrate the corrosion and/or cracking resistance of thermally treated Inconel 600 to primary and/or water, (ii) verify the corrosion and/or cracking resistance of the transi-tion of the lower joint of the sleeve, (iii) to verify the

. corrosion and/or cracking resistance of the upper joint of the sleeve; (iv) to verify leak limiting capabilities of the upper joint of the cleeve, (v) to verify the structural strength and.

leak tightness of the upper and -lower joint of the sleeve after cyclical loading and during accident conditions, (vi) to verify the internal pressure capabilities of sleeve joint, and (vii) any and all tests related to sleeving either not specifically referenced in the Sleeving Report and/or commenced subsequent to preparation of the Sleeving Report; and, with respect to each of the foregoing, provide all'detailstof the tests, if any.

Response

In addition to the documents identified in Licensee's response dated March 1,1982, the following documents contain information regarding this interrogatory:

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a 1. Report, NRC,' February 1982, NUREG 0886, " Steam Generator Tube

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Experience". .,

2. Report, EPRI, " Steam Generator Owners Group Plant, Superintendent and Plant Chemist Meeting of November 19-20, 13nE1".

3. Report, EPRI, February 1982, " Review of Intergranular Attack (IGA) of Alloy 600 Steam Generator Tubing".

4. Report, EPRI, April 13, 1982, " Optimization of Metallurgical Variables to Improve the Stress Corrosion Cracking Resistance of Inconel Alloy 600".

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8. State any and all studies, analyses or consideration of any kind given to the environment of either primary or secondary water in the annulus between the sleeve and the tube and/or to the poten-f al corrosive processes that might occur in that environment, apart .

from that specifically stated in Section 6.1 of +5? Sleeving l Report Jr in Section 6.1 of the San Onofre Repais. Report.

Response

In addition to the documents identified in Licensee's. response dated March 1, 1982, the following documents contain information regarding this interrogatory:

1. Letter, Sol Burstein, April 1, 1982, Response to G. H. Neils letter dated February 2,1982. '

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10. State any and all studies, analyses or consideration of any kind given to the inspectability and the accuracy of inspections of sleeved tubes, including but not limited to any results of inspec-tion of sleeved tubes in the field at any nuclear electric gener-ating plant, apart from that specifically stated in Section 7 of the Sleeving Report of Section 7 of the San onofre Repair Report.

Response

In addition to the documents identified in Licensee's response dated March 1,1982, the foll'owing documents contain information regarding the interrogatory:

1. Letter, Sol Burstein, April 1,1982, Response to G. H.Neils letter dated February 2,1982.

2. Memorandum, J. Schweitzer, March 5, 1982, " Point Beach Nuclear Plant- Unit 1 Spring 1982 Steam Generator Outage".

3. Letter, C. W. Fay,. January 25, 1982, " Sleeving Demonstration Pro-gram Point Beach Nuclear Plant Unit 1".

4. Memorandum, G. D. Frieling, March.16,1982, " Steam Generator Inspection Point Beach Nuclear Plant Unit:1".

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. 13. Please list all defects in steam generator tubes at Point Beach Nuclear Plant by unit, steam generator, row, column, date observed, and percent defect observed, which were at a height of 22" or higher ,

from tube end subsequent to 1975. '

Response

i In addition to the documents identified in Licensee's response dated March 1,1982, the following documents contain information regarding  !

this interrogator $y:

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1. Report, Westinghouse Field Service Report, "WEP-23, Unit 1 October 1981 Outage".

2. Memorandum, J. Schweitzer, March 12,1982, " Unit 1 Steam Gener- ,

ator Tube Plugging History". l

3. Letter, C. W. Fay, April 16, 1982, LER 82-007/01T-0, Notification of Degraded Steam Generator Tubes.

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, 14. State any and all studies, analyses or consideration of any kind l

given to observed defects in steam generator tubes at a height of 22" or higher from the tube end subsequent to 1975.

, Response l

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, . In addition to the documents identified in Licensee's response dated March 1, 1982, the following documents contain information regarding this interrogatory:

1. Memorandum, T. Colburn, March 5,1982, " Summary of the January 27, 1982 Meeting to Discuss Unit 1 Eddy Current Inspection Interval".

2. Report, Westinghouse FSR, WEP 23, " Unit 1, October 1981 Outage".

3. Letter, C. W. Fay, April 16, 1982, LER 82-007/01T-0, Notification of Degraded Steam Generator Tubes.

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, . 17. State any and all studies, analyses or consideration of the '

fall 1981 demonstration sleeving program at Point Beach Nuclear Plant Unit 1, apart from that included in the Sleeving Demonstra-

tion Report.

l Response i i'

The following documents contain information regarding this interrogatory:  !

1. Letter, C. W. Fay, January 25, 1982, " Sleeving Demonstration  !

Program Point Beach Nuclear Plant, Unit 1" (Proprietary)

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2. Westinghouse Field Service Report, WEP-24, " October / November, 1981 Channel Head Decon, Mechanical Plug Removal, Explosive Plug i Removal and Tube Sleeving.

3. Letter, Sol Burstein, April 1, 1982, Response to G. H. Neils

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t letter dated February 2, 1982. i i

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. 18. State the primary-to-secondary observed leak rate in Point Beach Nuclear Plant Unit 1 subsequent to completion on the fall 1981 sleeving demonstration program, including but not limited to the daily variation in such leak rate.

Response

. - The initial response to this interrogatory included the calcu-lated primary-to-secondary leak rates up to February 22, 1982. The follow-ing leak rates were calculated subsequent to February 22, 1982.

Date Leak Rate (GPD) 3/4/82 37 3/5/82 40 3/8/82 41 3/10/82 45 3/15/82 46 3/18/82 48 3/25/82 52 3/25/82-4/12/82 Unit 1 Outage 4/13/82 <10 Respectfully submitted, SHAW, PITTMAN, POTT & TROWBRIDGE By . r s BMeW. Churchill Delissa A. Ridgway Counsel for Licensee 1800 M St., N.W.

Washington, D.C. 20036 (202) 822-1000 Dated: April 30, 1982 l

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l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

,Before the Atomic Safety and Licensing Board In the Matter of )

)

WISCONSIN ELECTRIC POWER COMPANY ) Docket Nos. 50-266

) 50-301 (Point Beach Nuclear Plant ) (OL Amendment)

Units 1 and 2) )

AFFIDAVIT OF DAVID K. PORTER County of Milwaukee )

ss State of Wisconsin )

DAVID K. PORTER, being duly sworn according to law, deposes and says:

1. I am Manager of the Nuclear Engineering Section of the Nuclear Power Department of Wisconsin Electric Power Company. I graduated from the University of Illinois with a bachelor of science degree in electrical engineering in 1965. I then spent four years in the U.S. Navy's Nuclear Power Program which included one year in training and three years of reactor operator experience as an engineering officer aboard a nuclear powered cruiser. I joined the Nuclear Projects Office of Wisconsin Electric in 1969 and have been involved in various engineering assignments relating to the Point Beach Nuclear Plant and preconstruction nuclear projects since that time. As Manager of the Nuclear Engineering Section, I am responsible for providing technical, licensing, and engineering support to the Point Beach Nuclear Plant. These responsibilities include the technical review of plant equipment and repair specifications, and implementation of U. S. Nuclear Regulatory Commission ("NRC") licensing actions involving Wisconsin Elec-tric's operating nuclear facilities. I am personally familiar with Wisconsin

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Electric's activities concerning inspection and repair of the Point Beach Nuclear Plant steam generators and our application before the NRC with respect to these activities.

2. I have prepared or participated in the preparation of " Licensee's Supplemental Responses to Decade's First Interrogatories and Request for Production of Documents on the Full-Scale Sleeving Program", dated April 30, 1982. The information contained in those responses is true and correct to the best of my knowledge and belief.

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